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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Become a knowledge manager at UWC 2024
The American Nuclear Society is now accepting applications for knowledge managers to work during the 2024 Utility Working Conference and Vendor Technology Expo. This year’s UWC, “Nuclear Momentum: Advancing Our Clean Energy Future,” will be held August 4–7, 2024, at the JW Marriott Marco Island Beach Resort on Marco Island, Fla.=
Sunil Kumar Jatav, Vijay Kumar Pandey, Parimal P. Kulkarni, Arun K. Nayak, Upender Pandel, Rajendra K. Duchaniya
Nuclear Technology | Volume 208 | Number 11 | November 2022 | Pages 1756-1768
Technical Paper | doi.org/10.1080/00295450.2022.2061291
Articles are hosted by Taylor and Francis Online.
To mitigate severe accidents in nuclear reactors, the present research sheds light on the melt-coolability behavior of corium with hypothetical experiments that have been performed at two different nozzle diameters under bottom flooding conditions. In this research, a simulant material CaO-Fe2O3 powder mixture was melted and poured into the test section that was embedded in the test facility (using a bottom pouring furnace instead of a tiltable furnace). Then, from the bottom of the melt pool, water was flooded through a nozzle at a pressure of 0.70 bar and a water flow rate of 12 liters per minute. Because of the interaction between the water and melt, the melt quenched and converted into fine porous debris, and the temperature history was recorded using 12 K-type thermocouples connected to a data acquisition system. The average quenching time and porosity of the debris were affected by variations in the nozzle diameter. This research will help in understanding real core-melt accidents that generally occur in nuclear power plants.